Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Optimization of the ACR-700{sup TM} fuel management using gradient methods

Conference ·
OSTI ID:22039481
; ;  [1]
  1. Institut de Genie Nucleaire, Ecole Polytechnique de Montreal, Succ. Centre-ville, Montreal, Que. H3C 3A7 (Canada)
In the process of designing new reactors, fuel management optimization is an important step. Automatic fuel management optimization tools have been developed into the reactor core DONJON. Two gradient based methods are used to solve the optimization of the ACR-700 fuel management at equilibrium. Studies have been conducted to define the more appropriate method to adequately and efficiently reach an optimized exit burnup distribution for the ACR-700 core. Specific studies relevant to safety parameters are also presented. (authors)
Research Organization:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
22039481
Country of Publication:
United States
Language:
English

Similar Records

Effect of burnup on ACR-700 3-D reactivity devices cross sections
Conference · Sat Jul 01 00:00:00 EDT 2006 · OSTI ID:22039494

Optimal thorium-fueled CANDU nuclear reactor fuel management
Journal Article · Thu Feb 28 23:00:00 EST 1985 · Nucl. Technol.; (United States) · OSTI ID:5096827

Automatic optimized reload and depletion method for a pressurized water reactor
Journal Article · Sat Nov 30 23:00:00 EST 1985 · Nucl. Technol.; (United States) · OSTI ID:5986899